IR 05000370/1980014
| ML19343A753 | |
| Person / Time | |
|---|---|
| Site: | Mcguire |
| Issue date: | 10/07/1980 |
| From: | Bryant J, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19343A748 | List: |
| References | |
| 50-370-80-14, NUDOCS 8011210166 | |
| Download: ML19343A753 (5) | |
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f,,o NUCLEAR REGULATORY COMMISSION
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UNITED STATES
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- . E REGION 11
101 MARIETTA ST N.W., sulTE 31%
o ATLANTA, GEORGIA 30303
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Report ~No. 50-370/80-14 l
Licensee: Duke Power Company
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422 South Church Street
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Charlotte, NC 28242 i
Facility Name: McGuire, Unit 2
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Docket No. 50-370 License No. CPPR-84 Inspection at: McGuire Site near Lake Norman, North Carolina Inspector:
/#'/- d7 C'. R. McFarland Date Signed Approved by:
4M f,9/')k8 J
. Bryant, etion Chief, RCES Branch
' I) ate Signed SUMMART Inspection on September 3-5, 1980 Areas Inspected
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This routine announced inspection involved 19 inspector-hours on site in the areas of noncompliances, unresolved items, IE Bulletins, and licensee identified items.
Results Of the areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- J. C. Rogers, Project Manager
- T. E. Touchstone, Senior Construction Engineer
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W. O. Henry, QA Manager, Construction
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- E. B. Miller, Senior QA Engineer
- L. J. Bare, Assistant Engineer, Licensing
NRC Resident Inspector
- T. Donat,
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on September 5,1980 with those persons indicated in Paragraph I above. The inspector discussed his recent assignment as principal inspector for McGuire 2, and the need to review all cutstanding items.
3.
Licensee Action on Previous Inspection Findings a.
(0 pen) Infraction 370/80-01-01 Undersize socket welds. The inspector reviewed the corrective action program as stated in the licensee's responses to Region II dated March 5, March 27 and April 10, 1980.
The inspector reviewed the January 18, 1980 revision to the Process Control Manual, construction procedure (CP) 800 Section 6, issued July 7,1980 and nonconforming item reports (NCI) 10153, 10154, and 10728 through 10763. A review of inspection and inspection training records plus discussions with responsible DPC personnel indicated that adequate corrective action had been implemented to preclude future
. deficiencies in the weld sizes for nocket veld flanges and socket weld fittings. This it-m will rematu vpen pendin; IE examination of the welds.
b.
(Closed) Infraction 370/80-01-02, Missing drawing and improper subas-sembly dimension.
The inspector reviewed licensee's response to Region II dated March 5,.1980, NCI 10116 written to document the discrepuncy, and the records of the training of the appropriate craft personnel. The field installation isometric ISO MCF1-2 N154 has been revised to delete weld N12FW54-21.
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(Closed) Infraction 370/80-01-03, Inspector not knowing offset require-ment for final welded joint. The inspector reviewed the licensee's i
response to Region II dated March 5, 1980 and NCI 10232 written to document the deficiency. Training relative to the visual inspection
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and examination of welds, procedures L-80 and M-4, has been given to the QC welding inspectors with particular emphasis on the requirements for the fitup and offset of welds.
4.
Unresolved Items There were no new unresolved items identified during this inspection.
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5.
Independent Inspection
The inspector observed work inside the reactor building and the auxiliary ouilding, talked to various craf t personnel, and discussed construction
.i status with the project engineer. The current fuel loading date for Unit 2 is June,1982 6.
IE Bulletins (Closed) IEB 80-05, Vacuum Condition Resulting in Damage to Chemical a.
Volume Control System (CVCS) Holdup Tanks. The inspector reviewed the DPC response to Region II dated June 5,1980, and discussed the require-ments of the bulletin with the DPC staff. The subject tanks are designed to be protected against failure under vacuum conditions either by structural design or by venting.
b.
(Closed) IEB79-28, Possible Malfunction of Namco Model EA180 Limit
"4 Switches at Elevated Temperatures.
The inspector reviewed the DPC response to Region II dated February 5,1980 and discussed the require-ments of the bui'itin with the DPC staff. The subject switches have not been put inte service.
The inspector reviewed NCI 9381 which documents the replacement of the top gaskets in accordance with the
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Namco recommendations and the IEB 79-28 requirements.
c.
(Closed) IEB78-12, 12A and 12B, Atypical Weld Material in Reactor Pressure Vessel Welds. The NRC has completed the review of documenta-
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tion submitted by Westinghouse for the subject bulletin for the McGuire 2 reactor pressure vessel. DPC responses to Region II dated March 16, 1979, May 29, 1979, October 1, 1979 and November 7,1979 have been reviewed.
7.
Inspector Followup Item (IFI)
a.
(Closed) IFI 370/80-02-01, Followup on disposition of NCI 10348. The inspector reviewed the completed status of NCI 10248. The work was completed and accepted by QA on March 13, 1980. The QA review was completed March 20, 1980.
b.
(Open) IFI 370/80-14-10.
DPC Licensing Committment List. The DPC McGuire Committment List is used for tracking open items for Units 1 and 2.
There appears to be a need to verify that the appropriate Unit 2 items remain open when the work on an item common to both units is completed on Unit 1.
NRR initiated items are a case in point.
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Licensee Identified Items-(LII),10CFR50.55(e)
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- (Open) 370/80-14-01, Design deficiency 'in auxiliary feedwater system a.
(AFS) pumps. The licensee reported on-April 12, 1978 that'DPC had
. identified certain design criteria that relied on operator action for suction switchover for the AFS pumps. A safety-related instrumented 7-.
switchover system will be implemented. This item was not inspected.
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(Closed) 370/80-14-02, Undersized vent on refueling water storage tanks.. The inspector reviewed the DPC response to Region II dated
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July 21, 1978, reviewed drawing MC2406-23.43-00 August 4,1980, and observed the completed installation. Revision 14, issued
installation work was observed by an NRC inspector during the August 8 -
The completed
10, 1979 inspection.
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(open) 370/80-14-03, Dropped rod analysis deficiency. The DPC response c.
to Region II dated June 22, that Westinghouse Electric Company reported to the hT.1979 references a de i
in a March 30, 1979 letter, and a meeting of the NRC staff and Westinghouse on April 12 1979.
DPC will revise operating license to provide athe technical specifications issued for the
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lower setpoint for the high negative
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rate flux trip to provide adequate protection for any postulated rod drop accident.
Thi.: item waf. lot inspected.
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(0 pen) 370/80-14-04, Power operated relief valve (PORV) deficiency
The DPC responses to Region II. dated April 12,
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1979 and August 15, 1979 reported a binding problem with the PORV and identified the
action to be taken to correct the deficiency.
(0 pen) 370/80-14-05, Pipe hanger deficiencies. - The DPC 7.:sponse to e.
Region II dated May 11, 1979 of safety related pipe hangers. reported deficiencies.in the inspection
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initiated.
A revised inspection program has been f.
(0 pen) 370/80-14-06, Centrifugal charging pump (CCP) flow analysis.
The DPC response to Region II dated July 7, 1980 reported a potential
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flow deficiency for the McGuire CCP's.
to NRC by Westinghouse Electric Corporation letter NS-T MA-2245 dated
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May 8,1980'from T. M. Anderson to V. Stello.
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(0 pen) 370/80-14-07, Hydrogen purge system valve misapplication.. The DPC response to Region II dated August 4,1980 reported that a DPC Class E (ANSI B31.1) ~ valve had been erroneously assigned to an appli-
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cation requiring a Duke Class B (ASME III?' Tabre.
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The class E valve was:not' installed.
A qualified Class P h se has been selected and
installed.
This item was not inspectri F
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(Open) 370/80-14-08'
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The DPC response to Region II dated JalyDiesel genera,vr ca.rol air soleno
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25, 190,0 reported a deficiency
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in the subject valve for diesel generator IB.
A leaking vent ' solenoid i
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valve that. Lad not closed during testing of the diesel generator was identified. Four similar valves have been evaluated. Modifications will be made to the valves by January 1,- 1981.
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(Closed) 370/80-14-09, Defective coil leads in Valcor solenoid valves.
-The DPC response to Region II dated August 7 reported deficiencies in
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coil leads on Model V70900-21-3, S/N 738A to 745A and 746 to 807. All the subject valves have been replaced. The inspector reviewed NCI's 7862, '.A917, and 11343, -that. verified the corrective actions taken,
-the~traiaing records for the personnel, involved in changing the coils, and the procedure used to control the valve replacement work.
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